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Book Uranium Recovery from Slag by Fluoride Volatilization

Download or read book Uranium Recovery from Slag by Fluoride Volatilization written by R. M. Edwards and published by . This book was released on 1958 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Processing of Uranium magnesium Fluoride Slag

Download or read book Processing of Uranium magnesium Fluoride Slag written by U.S. Atomic Energy Commission and published by . This book was released on 1956 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Uranium Recovery from Composite UF4 Reduction Bomb Wastes

Download or read book Uranium Recovery from Composite UF4 Reduction Bomb Wastes written by E. R. Johnson and published by . This book was released on 1954 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Recovery of Uranium and Fluorine from Quenched Phosphate Slag

Download or read book Recovery of Uranium and Fluorine from Quenched Phosphate Slag written by C. M. Wai and published by . This book was released on 1982 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Applications of Fluoride Volatility Processes to Feed Materials

Download or read book Applications of Fluoride Volatility Processes to Feed Materials written by Robert K. Steunenberg and published by . This book was released on 1957 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Solvent Extraction of Uranium from Reduction Slag Slurry

Download or read book Solvent Extraction of Uranium from Reduction Slag Slurry written by A. D. Ryon and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1964-10 with total page 1668 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Magnesium Fluoride Recovery Method

Download or read book Magnesium Fluoride Recovery Method written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A method of obtaining magnesium fluoride substantially free from radioactive uranium from a slag containing the same and having a radioactivity level of at least about 7000 pCi/gm. The slag is ground to a particle size of about 200 microns or less. The ground slag is contacted with an acid under certain prescribed conditions to produce a liquid product and a particulate solid product. The particulate solid product is separated from the liquid and treated at least two more times with acid to produce a solid residue consisting essentially of magnesium fluoride substantially free of uranium and having a residual radioactivity level of less than about 1000 pCi/gm. In accordance with a particularly preferred embodiment of the invention a catalyst and an oxidizing agent are used during the acid treatment and preferably the acid is sulfuric acid having a strength of about 1.0 Normal.

Book Uranium Production Technology

Download or read book Uranium Production Technology written by Charles D. Harrington and published by . This book was released on 1959 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Precipitation of Uranium Peroxide in the Presence of Fluorides

Download or read book The Precipitation of Uranium Peroxide in the Presence of Fluorides written by and published by . This book was released on 1941 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The large-scale recovery of uranium from materials which also contained great quantities of fluorides did not give a product which had a low enough fluoride content to be treated satisfactorily by the other extraction process. The objective of the investigations carried out in this laboratory was a method of reducing the amount of fluoride which accompanied the uranium. The material from which the uranium was recovered in the industrial process was a slag containing (in addition to uranium) magnesium fluoride, calcium and dolomitic lines, crucible dross, and other waste products from the reaction of magnesium metal and uranium hexafluoride. Most of the fluoride was removed from this mixture by heating the roasted and ground slag with sulfuric acid. The residue was mixed with water and much of the caclium sulfate and fluoride, magnesium fluoride, and hydrated ferric oxide and alumina was precipitated by reducing the acidity. After filtering off the precipitate, ammonium sulfate was added to the solution and uranium peroxide (UO4 · 2H2O) was precipitated by addition of hydrogen peroxide. The pH of the solution was maintained between 3.0 and 3.5 during the precipitation by addition of sodium hydroxide. The uranium peroxide, even after washing, contained between 2 and 3% fluoride. The percentage of fluoride could be reduced to 0.5% by precipitating the peroxide from a more acidic solution but this required the use of much larger amounts of hydrogen peroxide.

Book Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel

Download or read book Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The overall objective of this study was to support an alternative hybrid process to meet Advanced Fuel Cycle Initiative (AFCI) goals, using fluorination and aqueous processing techniques, for treatment of spent nuclear fuel (SNF). The specific goal was to develop a simple aqueous dissolution process to separate two high-heat fission products, cesium and strontium, from SNF fluoride residues. This separation study was based on solubility differences examined by modeling using the HSC Chemistry 5.0 and OLI Stream Analyzer 1.2 programs. HSC automatically utilizes an extensive thermochemical database, which contains enthalpy (H), entropy (S), and heat capacity (Cp) data for more than 17,000 chemical compounds. The OLI Stream Analyzer 1.2 program is the result of over 30 years of effort and represents the state-ot-the-art technology in aqueous solution simulation. The work focused on the fluoride residues from the voloxidation and fluorination steps of the fluoride volatility process and was limited to SNF from commercial light-water reactors. Material balances were used to estimate the quantity of residue. A representative SNF was considered to be one with a burnup of 33,000 megawatt days per metric tonne initial heavy metal (MWd/MTIHM) after a 10-year cooling period, from a pressurized-water reactor (PWR). The dry fluorination method was used for uranium removal. The work described in this paper was based solely on computer modeling, which may serve as the basis for any necessary follow-on laboratory validation experiments. Observations from this study showed that the separation of fluoride residues by a simplified, alternative aqueous process is practical. The simulated process could be carried out at 1 atm and 30-50C̊. The OLI model showed separation of cesium and strontium was possible with only one dissolution with water, whereas the HSC model indicated two dissolutions would be required. Plutonium and Np were removed together, which would maintain proliferation resistance. Because this research was based on computer modeling, follow-on laboratory experiments are necessary to validate the results and to improve the process flow diagram. Further development of the process flow diagram, with equipment design and cost estimation, is also recommended.

Book Spray Fluorination of Fused Salt as a Uranium Recovery Process

Download or read book Spray Fluorination of Fused Salt as a Uranium Recovery Process written by J. D. Gabor and published by . This book was released on 1960 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt: Spray fluorination may be used to recover uranium as the volatile hexafluoride from molten fluorides by spraying the salt into a fluorine atmosphere. This drop-wise liquid fused-salt fluoride volatility process applied to zirconium-matrix fuels, with the possible advantage of avoiding corrosive conditions involved in sparging. Experimental equipment was developed and tests were made for heat and mass transfer. From the data obtained, process design calculations indicated that a satisfactory equipment design is possible.